A Time Dependent Transport Equation Solver

Abstract

A new time dependent neutron and photon transport code was developed. The code, FMP2DT (Finite element, Multigroup, P sub n, 2-Dimensional, Time dependent), was discretized in space using finite elements, discretized in energy using a multigroup approximation, and discretized in time using Euler' backward differencing scheme. Its angular flux dependency was discretized using spherical harmonics. A P sub 1 angular flux approximation allows some modeling of both anisotropic flux behavior and wave behavior. FMP2DT can model radiation transport in XZ slab or RZ cylindrical geometry. An inherently stable iteration solution scheme, an incomplete Cholesky conjugate gradient algorithm, calculates the total flux coefficients. FMP2DT was benchmarked against exact flux calculations in infinite XZ and RZ geometries. Two problems were solved by FMP2DT which involved the observation of the flux decay after injection of an inhomogeneous pulsed source to the configurations. A nuclear reactor, initially critical, had a pulsed source introduced at its center. This is typically done in so called Rossi-alpha experiments. FMP2DT showed that time must be allowed so that only the fundamental mode is dominant or the flux data will not yield credible information to calculate alpha. A uranium borehole problem was solved where FMP2DT showed that a counting instrument must be calibrated for different distances from a pulsed source because the flux decays with a different decay constant for each spatial point. Previous models did not account for this diffusion effect.

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Document Details

Document Type
Technical Report
Publication Date
May 01, 1991
Accession Number
ADA239329

Entities

People

  • Lennard W. Lee Jr.

Organizations

  • Air Force Institute of Technology

Tags

Communities of Interest

  • Energy and Power Technologies

DTIC Thesaurus Topics

  • Air Force
  • Boltzmann Equation
  • Computational Fluid Dynamics
  • Computational Science
  • Differential Equations
  • Equations
  • Fission Neutrons
  • Geometry
  • Neutron Flux
  • New Mexico
  • Nuclear Engineering
  • Nuclear Reactors
  • Partial Differential Equations
  • Prompt Neutrons
  • Radiative Transfer
  • Theses
  • Two Dimensional

Fields of Study

  • Physics

Readers

  • Computational Modeling and Simulation
  • Finite Element Method (FEM) for solving Partial Differential Equations (PDEs)
  • Nuclear and Radiation Engineering.

Technology Areas

  • Space
  • Space - Hall-Effect Thruster